2023 Fall Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[3A06-09] Fuel Cladding Materials 2

Fri. Sep 8, 2023 10:55 AM - 12:00 PM Room A (IB Bildg.1F IB013)

Chair:Hiroaki ABE(UTokyo)

11:25 AM - 11:40 AM

[3A08] R&D for Introducing Silicon Carbide Materials to Safety Improvement of BWR’s Core

(10) Joint Strength Evaluation of End-plug Joints in SiC Tubes at a Simulated Severe Accident (3)

*Ryo Ishibashi1, Kazuma Hirosaka1, Masatoshi Shibata1, Masana Sasaki1, Yoshiyuki Nemoto2 (1. HGNE, 2. JAEA)

Keywords:Accident tolerant fuel, Silicon carbide, End-plug joining, Severe accident, High temperature strength

炭化ケイ素(SiC)製燃料被覆管には事故時に高い耐熱性を期待している。強度上の課題となりうる端栓接合部に対して事故時を想定した高温荷重に対する健全性の評価を目的に、解析により荷重負荷時の端栓接合部での変形挙動に及ぼす製造時における詳細構造寸法のばらつきの影響を検討した。

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